Overview of safety improvement during RBMK-1500 reactor core lifetime upgrading
- Resource Type
- Authors
- Aurimas Tonkunas; Raimondas Pabarčius; M. Seporaitis; Andrius Slavickas
- Source
- Scopus-Elsevier
- Subject
- Nuclear and High Energy Physics
Radiation
Safety design
Nuclear engineering
Shutdown
Core (manufacturing)
First generation
Nuclear Energy and Engineering
Nuclear reactor core
Boiling
RBMK
Environmental science
General Materials Science
Three generations
Safety, Risk, Reliability and Quality
- Language
Starting from early to mid 1970s the first generation of channel-type graphite-moderated boiling water reactors socalled RBMK types were designed and went into operation. Nowadays, all designed RBMKs represent three generations of reactors having significant differences with respect to their safety design features. The Ignalina NPP with two RBMK-1500 units being a second generation type were originally the most powerful reactors in the world. The change of important neutron-physical characteristics, being specific safety features for RBMK type reactors during RBMK-1500 core upgrading processes are analyzed until final shutdown and their impact on safety during reactor lifetime is discussed.